ML15264A342
| ML15264A342 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/06/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8509160433 | |
| Download: ML15264A342 (11) | |
Text
September 6, 1985 Dockets Nos. 50-269, 50-270 DISTRIBUTION and 50-287
'Docket File RIngram NRC PDR HNicolaras L PDR Gray File ORB#4 Rdg EBrach Mr. Hal B. Tucker HThompson HOrnstein Vice President - Nuclear Production OELD WPaulson Duke Power Company EJordan GEdison P. 0. Box 33189 BGrimes PGuill 422 South Church Street JPartlow Charlotte, North Carolina 28242 ACRS-10
Dear Mr. Tucker:
SUBJECT:
LOW-LEVEL WASTE INCINERATOR - REQUEST FOR ADDITIONAL INFORMATION Re:
Oconee Nuclear Station, Units 1, 2 and 3 We have reviewed your June 10, 1985 submittal requesting approval to operate a low level radioactive waste incinerator at the Oconee Nuclear Station. We have determined that we need additional information to complete our review.
We request that you respond to the enclosed list of questions within 30 days of receipt of this letter. This request for additional information affects fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
As Stated cc w/enclosure:
See next page 0H.DL ORB H oaras;cr JSto L /j/85
/
8509160433 850906 PDR ADOCK 05000269
- PDR,
Mr. H. B. Tucker Oconee Nuclear Station Duke Power Company Units Nos. 1, 2 and 3 cc:
Mr. William L. Porter Duke Power Company P. 0. Box 33189 422 South Church Street Charlotte, North Carolina 28242 J. Michael McGarry, III, Esq.
Bishop,.Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.
Washington, D.C. 20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610
\\
Seneca, South Carolina., 29678 Regional Administrator U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 3100 Atlanta, Georgia 30303 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621
REQUEST FOR ADDITIONAL INFORMATION OCONEE WASTE VOLUME REDUCTION INCINERATOR A. Effluent Treatment Systems
- 1. In its reviews, the staff, where appropriate, performs independent calculations of the rates of release of radioactive materials to the environment. For this, the staff utilizes the GALE computer code, NUREG-0017 (for PWRs), and information supplied by the applicant.
To calculate the rates of release of radioactive materials from the Oconee Nuclear Station due to the operation of the Radioactive Waste Volume Reduction Incinerator we find that we need the following additional information:
(1) Capacity of collection tanks for liquid wastes to be processed through the evaporators; (2) Description of any ion exchange processing of liquid wastes prior to evaporation; (3) Processing rate of the evaporator; (4) Capacity of tanks for collecting and holding evaporator bottoms prior to processing by the VR system; (5) Rate of feed of evaporator bottoms to VR system processing; (6) Average time that powdex filters are in service for secondary coolant; (7) Holdup time for powdex filters after end of service and prior to initiation of feed to the VR system;
(8) Rate of feed.of secondary resin to the VR system for processing; and (9) Detailed basis and methodology of the Duke Power Company estimate of the annual station volumetric production and expected activity feed rate of waste to the VR system for evaporator bottoms, combustible trash, powdex resins and contaminated oils.
- 2. Describe the location and elevation of the point of release to the environment of radioactive effluents from the VR system; and provide characteristics of the releases from the stack, i.e., velocity, temperature and direction. (See question 8.1.)
- 3. Describe the additional annual volumes, types, forms, and curies of principal radionuclides and others radionuclides that will be disposed of as radioactive solid waste as a result of VR system operation.
- 4. Describe limits to be maintained for controlling the quantities of feed materials that might bring about detrimental non-radiological effects on the environment due to effluents from the YR system operation.
- 5. Provide an estimate of the effect of the recycle of VR system condensate to the liquid radwaste sytem on the radioactive liquid effluents from the plant.and on offsite doses due to the radioactive liquid effluents.
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- 6. Describe provisions for monitoring and sampling airborne releases to the environment from the VR system and for alarms and automatic control features associated with these monitors.
- 7. Describe provisions for in-place area radiation monitoring in the various VR system cubicles to determine leaks from the VR system and for alarms and automatic control features associated with these monitors.
- 8. Describe how the VR system off-gas subsystem is constructed, and will be operated, maintained, and tested, in accordance with the intent of Regulatory Guide 1.140.
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- 9. Describe any further. treatment of YR system effluents downstream of the off-gas filters.
- 10. Describe the degree of conformance to Regulatory Guide 1.143, Regulatory Positions 1.1.3, 1.2.1 through 1.2.4, 4.1 and 5.2 involving seismic design criteria for foundations and walls of structures that house the VR system tanks containing liquid radwaste; monitoring and alarming of liquid tank levels and curbing of indoor tanks; routing drains, overflows and sample lines to the liquid radwaste system; provisions for prevention of contamination
4 of unmonitored or non-radioactive systems or ductwork; and seismic design criteria for buildings housing the VR system.
- 11.
Describe the degree of conformance to Regulatory Guide 1.143, Regulatory Position 6, on quality assurance.
- 12. Describe limits to be maintained for controlling the quantities of feed materials, e.g., halogenated plastics, sulfur in contaminated oil, that might be detrimental to the safe and effective performance of the VR and other systems, e.g., radwaste building-ventilation exhaust, liquid radwaste.
- 13. Describe provisions to assure adequate training of VR system operation and maintenance personnel.
- 14. Provide details of compliance with Branch Technical Position CMEB 9.5.1 concerning fire protection.
- 15.
Provide the detailed basis and methodology for the source terms used in the accident analyses.
- 16. Provide the methodology for determining gaseous effluent activity concentrations in unrestricted areas relative to 10 CFR 20, Appendix B, concentration limits, considering all gaseous effluents from the Oconee site.
-5 B. Meteorology
- 1. Atmospheric dispersion parameters such as relative concentration (X/Q) and relative deposition (D/Q) are dependent on location of releases, release characteristics (e.g., particle size, temperature, exit velocity, stack diameter, and duration) and influences of plant structures and terrain features. Provide a description of the release point(s),
release characteristics, and other plant structures and/or terrain features which influence atmospheric transport and diffusion for both accidental releases and releases from normal operations of the incinerator.
- 2. Considering the release point(s) and release characteristics described in response to RAI #1'-above, provide a description of the atmospheric dispersion model used to calculate appropriate X/Q and D/Q values for accidental and normal releases including specification of and justification for model input information such as release mode (e.g.,
ground level, elevated, or a mixture of ground level and elevated),
characteristic building shapes (height and cross-sectional area), and meteorological data base (period of record and distributions.of wind speed, wind direction, and atmospheric stability).
For example,
-6 a characteristic building wake factor, CA, of 1270m2 is assumed for evaluating short-term accidental releases (Section 3.2 page 40).
This is a value typically assumed for accidental releases from or in the immediate vicinity of the reactor building, and.may or may not be applicable to accidental releases from the incinerator. No comparable building information is presented in either this document or in the cross referenced Offsite Dose Calculation Manual (ODCM) for consideration in evaluating normal releases from the incinerator.
- 3. Table 2.3.3, "Site Boundary Concentrations from Normal Operations," is apparently based on a X/Q value of 4.1X10-7 sec/m3 representative of.a "maximum location at 3.5 miles" south of the facility. However, site boundary distances presented or implied in Tables A4.0-1, A4.0-2, and A5.0-1 of the ODCM appear to be at considerably smaller distances.
Provide justification for the use of a X/Q value of 4.1X10-7 sec/m3 to represent maximum annual average atmospheric dispersion information at or beyond the site boundary for releases from the incinerator, considering release point and release characteristc information provided in response to RAI #1 above and atmospheric dispersion modeling information provjded in response to RAI #2 above.
- 4. From the descriptions of the airborne releases from normal operations (Section 2.3.1) and of the potential accidental releases (Section 3.1),
-7 atmospheric deposition could be a significant dose pathway for particles and radioiodines released from the incinerator. Provide a discussion of atmospheric deposition of particles and radioiodines from normal and accidental releases, and, if deposition is a significant dose pathway, provide estimates of relative deposition (D/Q) at appropriate locations, considering information provided in response to RAls #1 and #2 above.
- 5. Provide more specific information on meteorological data used to represent atmospheric transport and diffusion characteristics (see RAI
- 2 above) and expand Section 6.3, "Meteorological Data," accordingly.
Also, Section 6.3 should include specific meteorological conditions (e.g., extreme winds and tornadoes) considered in the design of the radwaste facility structure alluded to in Section 5.0.
-8 C. Occupational Exposure
- 1. Provide layout drawings showing the arrangement of the VR system at Oconee. In these drawings, include all major radwaste components, all shield walls, area radiation zones, and locations of area radiation monitors.
- 2. In section 4.2 of your radwaste volume reduction incinerator submittal, you state that "all the major components" will be provided with decontamination nozzles. Provide a listing of all components that will.have decontamination nozzles and describe the precautions taken to minimize personnel exposures during the remote cleaning of these N
decontamination nozzles should these nozzles become clogged.
D. Exposure of the General Public
- 1. Describe the disposition of the solid wastes to be generated by operation of the VR system.
- 2. Provide the proposed changes to the Radiological Effluent Technical Specifications (RETS) for the Oconee Nuclear Station.
- 3. Provide DPC's proposed changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP) for the Oconee Nuclear Station. The ODCM should include source terms from the VR system to assure compliance with the dose design objectives of 10 CFR 50 App. I.
- 4. On p. 26, footnote 1 to Table 2.3.2, it is stated that the "total body doses evaluated at a location where the highest radiation dose to the whole body... has been estimated." - Provide the location in terms of distance and direction from the release point in relation to the coordinate system used in the 00CM.